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Journal Articles

Overview on recent progress toward small specimen test technique

Wakai, Eiichi; Kikuchi, Takayuki; Kim, B.*; Kimura, Akihiko*; Nogami, Shuhei*; Hasegawa, Akira*; Nishimura, Arata*; Soldaini, M.*; Yamamoto, Michiyoshi*; Knaster, J.*

Fusion Engineering and Design, 98-99, p.2089 - 2093, 2015/10

 Times Cited Count:16 Percentile:77.56(Nuclear Science & Technology)

Journal Articles

Current status of the engineering design of the test modules for the IFMIF

Yamamoto, Michiyoshi; Arbeiter, F.*; Yokomine, Takehiko*; Wakai, Eiichi; Theile, J.*; Garcia, A. S.*; Rapisarda, D. S.*; Casal, N. I.*; Mas, A. S.*; Gouat, P.*; et al.

Fusion Engineering and Design, 88(6-8), p.746 - 750, 2013/10

 Times Cited Count:14 Percentile:72.14(Nuclear Science & Technology)

Under Broader Approach (BA) Agreement between EURATOM and Japan, IFMIF/EVEDA (International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activities) has been performed since the middle of 2007. The present EVEDA phase aims at producing a detailed, compete and fully integrated engineering design of IFMIF. The deivery of the Intermediate IFMIF engineering design report is foreseen mid-2013. The main function of the IFMIF is to provide the materials database for the design and licensing of DEMO reactor and further fusion rectors from the material sets irradiated in High Flux Test Modules (HFTM, Startup Monitoring Module), Medium Flux Test Modules (Creep Fatigues Test Module, Tritium Release Test Module, Liquid Breeder Validation Module) and Low Flux Test Modules of IFMIF. This paper is summarizing the current progress of the engineering design of the test modules within the IFMIF/EVEDA project.

Journal Articles

Analysis of test matrix and design status of test modules of IFMIF

Wakai, Eiichi; Kikuchi, Takayuki; Yokomine, Takehiko*; Yamamoto, Michiyoshi; Soldaini, M.*; Polato, A.*

Fusion Science and Technology, 62(1), p.246 - 251, 2012/07

 Times Cited Count:6 Percentile:43.52(Nuclear Science & Technology)

Journal Articles

Basic design guideline for the preliminary engineering design of PIE facilities in IFMIF/EVEDA

Kogawara, Takafumi; Wakai, Eiichi; Kikuchi, Takayuki; Yamamoto, Michiyoshi; Molla, J.*

Fusion Engineering and Design, 86(12), p.2904 - 2907, 2011/12

 Times Cited Count:3 Percentile:26.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Workload foreseen for the IFMIF Post Irradiation Examination Facility

Molla, J.*; Yamamoto, Michiyoshi; Polato, A.*; Soldaini, M.*; Takeuchi, Hiroshi; Wakai, Eiichi

Fusion Engineering and Design, 86(9-11), p.2522 - 2525, 2011/10

 Times Cited Count:3 Percentile:26.02(Nuclear Science & Technology)

The workload for the Post Irradiation Examination facility during the operation of IFMIF is evaluated in this paper are based on the IFMIF specifications proposed by IFMIF user's community, available irradiation volumes in the test modules and materials properties required to compile the materials database.

Journal Articles

Design plan and requirement of test module and testing items in IFMIF

Wakai, Eiichi; Yamamoto, Michiyoshi; Molla, J.*; Yokomine, Takehiko*; Nogami, Shuhei*

Fusion Engineering and Design, 86(6-8), p.712 - 715, 2011/10

 Times Cited Count:6 Percentile:44.28(Nuclear Science & Technology)

The main purpose of present phase of IFMIF/EVEDA (International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activities) is to produce a detailed report of IFMIF engineering design with the integrated design of all facilities in IFMIF. The main function of the IFMIF is to give the demanded design database for the licensing of DEMO reactors and further reactors, and it is achieved from the materials data set obtained from the high, medium, and low flux test modules (HFTM, MFTM and LFTM) of IFMIF. In the evaluation using small specimens, developments and guidelines of small specimen test technique or technology (SSTT) are also demanded for the achievements. This paper is summarized about the design plan and requirements in these test modules and testing items in IFMIF.

Oral presentation

Recent progress of test facilities in IFMIF/EVEDA project

Wakai, Eiichi; Kogawara, Takafumi; Kikuchi, Takayuki; Yokomine, Takehiko*; Molla, J.*; Yamamoto, Michiyoshi

no journal, , 

no abstracts in English

Oral presentation

Activity status of Japanese team of test facilities in IFMIF/EVEDA project

Wakai, Eiichi; Kogawara, Takafumi; Kikuchi, Takayuki; Yamamoto, Michiyoshi; Molla, J.*; Kimura, Akihiko*; Kasada, Ryuta*; Kim, B.*; Nogami, Shuhei*; Hasegawa, Akira*; et al.

no journal, , 

no abstracts in English

Oral presentation

Progress of engineering design in IFMIF-EVEDA project

Wakai, Eiichi; Kikuchi, Takayuki; Hirano, Michiko; Ida, Mizuho; Niitsuma, Shigeto; Kimura, Haruyuki; Nishitani, Takeo; Yamamoto, Michiyoshi; Matsumoto, Hiroshi; Sugimoto, Masayoshi; et al.

no journal, , 

no abstracts in English

Oral presentation

Status of lithium target facility development in IFMIF/EVEDA project

Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Nakaniwa, Koichi; Ito, Yuzuru; Tanaka, Hiroshi; Tsuji, Yoshiyuki*; Ito, Takahiro*; et al.

no journal, , 

no abstracts in English

Oral presentation

Activities summary on lithium target system and test facilities in IFMIF/EVEDA Project, 7; Engineering design of lithium target and post irradiation examination facilities in IFMIF

Sugimoto, Masayoshi; Wakai, Eiichi; Kanemura, Takuji; Kikuchi, Takayuki; Ida, Mizuho*; Watanabe, Kazuyoshi*; Niitsuma, Shigeto*; Yamamoto, Michiyoshi*; Yutani, Toshiaki*; Hirano, Michiko*

no journal, , 

The International Fusion Materials Irradiation Facility - Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) is a EU an Japan collaborative project under the framework of the Broader Approach activities for fusion energy development and, after the Intermediate Engineering Design Report has been completed in 2013, the validation test tasks have been conducted up to 2015. About the tasks in charge of Japan were completed in March and now we continue the evaluation of the testing results and examine how to reflect them to updated engineering design. In this report, we present the technical validity of the design based on the results of various validation tests and summarize the issues to be solved in future.

11 (Records 1-11 displayed on this page)
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